Volume 2
Number 2
Fast Neutron Damaging in Nuclear Reactors. II. The Radiation Damage Function of Graphite
Nuclear Science and Engineering / Volume 2 / Number 2 / April 1957 / Pages 117-125
Technical Paper / dx.doi.org/10.13182/NSE57-A25381
Radioactive Carry-Over from Borax-III and Test Systems
Nuclear Science and Engineering / Volume 2 / Number 2 / April 1957 / Pages 126-142
Technical Paper / dx.doi.org/10.13182/NSE57-A25382
Attenuation of 14.1-Mev Neutrons in Water
Nuclear Science and Engineering / Volume 2 / Number 2 / April 1957 / Pages 143-159
Technical Paper / dx.doi.org/10.13182/NSE57-A25383
Engineering Data for Diphenyl Cooled Nuclear Reactors
Nuclear Science and Engineering / Volume 2 / Number 2 / April 1957 / Pages 160-169
Technical Paper / dx.doi.org/10.13182/NSE57-A25384
Spatial Distribution of Thermal Neutrons from an N17 Source in Water
Nuclear Science and Engineering / Volume 2 / Number 2 / April 1957 / Pages 170-180
Technical Paper / dx.doi.org/10.13182/NSE57-A25385
Measurement of Local Heat Transfer Coefficients with Sodium-Potassium Eutectic in Turbulent Flow
Nuclear Science and Engineering / Volume 2 / Number 2 / April 1957 / Pages 181-198
Technical Paper / dx.doi.org/10.13182/NSE57-A25386
Neutron Thermalization: II. Heavy Crystalline Moderator
Nuclear Science and Engineering / Volume 2 / Number 2 / April 1957 / Pages 199-212
Technical Paper / dx.doi.org/10.13182/NSE57-A25387
Thermal Stresses in Clad Fuel Plates
Nuclear Science and Engineering / Volume 2 / Number 2 / April 1957 / Pages 213-218
Technical Paper / dx.doi.org/10.13182/NSE57-A25388
